丛烁｜厦门大学嘉庚学院｜学者主页

2026

Investigation of the mechanical and microstructural properties of a novel Zirconium alloy

Guannan Zhao, Hongchang Wang, Yibin Tang, Yizhong Yang, Shuo Cong, Guan-Ze He

Journal of Physics, Conference Series

DOI

2026

Misorientation angle-dependent anomalous preferential nucleation of dislocation loop at grain boundary in irradiated aluminum alloys

Zuojiang Wang, Ziqi Cao, Ling Li, Yizhong Yang, Zhengyu Liu, Hongchang Wang, Guan-Ze He, Shuo Cong, Xu-Jia Wang, G. Ran

Acta Materialia

DOI

2025

Differential effects of Si/dpa ratio on the evolution of dislocation loops in Al-2.64Mg alloy during in-situ irradiation

Shuo Cong, Ming Cao, Zuojiang Wang, Ziqi Cao, Ling Li, Yizhong Yang, Zhengyu Liu, Xu-Jia Wang, G. Ran

Journal of Nuclear Materials

DOI

2025

In-situ simulation of transmutation-produced Si-containing precipitates of Al alloys via Si ion irradiation

Shuo Cong, Ming Cao, Zuojiang Wang, Shikun Zhu, Ziqi Cao, Ling Li, Yizhong Yang, Zhengyu Liu, Xu-Jia Wang, G. Ran

Journal of Nuclear Materials

DOI

2025

Exploring differences in irradiation-induced defects between Mg2Si and Si-rich precipitates in Al-alloys

Zuojiang Wang, Xu-Jia Wang, Zhengyu Liu, Ziqi Cao, Ling Li, Yizhong Yang, Hongchang Wang, Shuo Cong, G. Ran

Journal of Nuclear Materials

DOI

2025

Synthesis and density optimization of fluorite-structured Dy2TiO5 neutron-absorbing powder via a melting–crushing–grading route

Lingling Luo, Sheng-You Zhu, Duyue Chen, Junfui He, Zilong Cao, Duojun Zhong, Tianhao Wang, Shuo Cong

AIP Advances

DOI

2025

Intuitively revealing the dominant inhibitory effect of silicon on the formation of super-size dislocation loop in Al-Mg alloys

Zuojiang Wang, Ziqi Cao, Ling Li, Zhengyu Liu, Yizhong Yang, Yibin Tang, Shuo Cong, Xu-Jia Wang, G. Ran

Journal of Materials Science & Technology

DOI

2024

In-situ study on the differential evolution of He bubbles in the multilayer oxide of Fe9Cr1.5W0.4Si F/M steel corroded in lead-bismuth eutectic

Dewang Cui, Shuo Cong, Ziqi Cao, Fan Yuan, G. Ran

Journal of Nuclear Materials

DOI

2024

In-situ investigation of helium effect on diverse precipitate/matrix interface areas in irradiated 5052 aluminum alloy

Zuojiang Wang, Ziqi Cao, Ling Li, Zhengyu Liu, Yizhong Yang, Shuo Cong, Hongchang Wang, Yibin Tang, Xu-Jia Wang, G. Ran

Surfaces and Interfaces

DOI

2022

Understanding the stress corrosion cracking growth mechanism of a cold worked alumina-forming austenitic steel in supercritical carbon dioxide

Zhu Liu, Jiachen Long, H. Su, Shuo Cong, Kai Chen, Peng Wang, Z. Duan, Zhaodan Ma, Zhang-Jian Zhou, Le-Fu Zhang, Xiang-Long Guo

Corrosion Science

DOI

2021

High-temperature corrosion behavior of hot-pressed Al-based Gd2O3-W shielding materials used in spent fuel storage

Shuo Cong, Yi-Peng Li, G. Ran, Wei Zhou, Shi-Gang Dong, Q. Feng

Corrosion Science

DOI

2021

Early-stage corrosion behavior of Al-based Gd2O3–W shielding composites in a simulated spent fuel wet storage environment

Shuo Cong, G. Ran, Yi-Peng Li, Shi-Gang Dong, Xiuyin Huang

Progress in nuclear energy (New series)

DOI

2020

乏燃料储存用含Gd和W元素的Al基屏蔽复合材料的研制

丛烁

《厦门大学》

2020

Investigation of Microstructure and Nanoindentation Hardness of C+ & He+ Irradiated Nanocrystal SiC Coatings during Annealing and Corrosion

Guiliang Liu, Yi-Peng Li, Zongbei He, Yang Chen, Shuo Cong, Zhao-Ke Chen, Xiuyin Huang, Rui-Qian Zhang, G. Ran

Materials

DOI

2020

Microstructure characteristics of C+ and He+ irradiated SiCf/SiC composites before and after annealing

Guiliang Liu, G. Ran, Zongbei He, Chao Ye, Yi-Peng Li, Xin-Yi Liu, Yang Chen, Zhao-Ke Chen, Shuo Cong, Rui-Qian Zhang, Xiuyin Huang

DOI

2020

Microstructure and its effect on mechanical and thermal properties of Al-based Gd2O3 MMCs used as shielding materials in spent fuel storage

Shuo Cong, Yi-Peng Li, G. Ran, Wei Zhou, Q. Feng

DOI

2020

Early corrosion behaviour of irradiated FeCrAl alloy in a simulated pressurized water reactor environment

Weisong Wu, G. Ran, Yi-Peng Li, Shuo Cong, Chao Ye, Rui-Qian Zhang, Yong-duo Sun

DOI

2020

Ball-milling properties and sintering behavior of Al-based Gd2O3–W shielding materials used in spent-fuel storage

Shuo Cong, G. Ran, Yi-Peng Li, Yang Chen

Powder Technology

DOI

2018

Stress Corrosion Behaviors of 316LN Stainless Steel in a Simulated PWR Primary Water Environment

Yong Huang, Weisong Wu, Shuo Cong, G. Ran, Dan-Xia Cen, Ning Li

Materials

DOI

丛烁

精选作品

期刊论文

Investigation of the mechanical and microstructural properties of a novel Zirconium alloy

Misorientation angle-dependent anomalous preferential nucleation of dislocation loop at grain boundary in irradiated aluminum alloys

Differential effects of Si/dpa ratio on the evolution of dislocation loops in Al-2.64Mg alloy during in-situ irradiation

In-situ simulation of transmutation-produced Si-containing precipitates of Al alloys via Si ion irradiation

Exploring differences in irradiation-induced defects between Mg2Si and Si-rich precipitates in Al-alloys

Synthesis and density optimization of fluorite-structured Dy2TiO5 neutron-absorbing powder via a melting–crushing–grading route

Intuitively revealing the dominant inhibitory effect of silicon on the formation of super-size dislocation loop in Al-Mg alloys

In-situ study on the differential evolution of He bubbles in the multilayer oxide of Fe9Cr1.5W0.4Si F/M steel corroded in lead-bismuth eutectic

In-situ investigation of helium effect on diverse precipitate/matrix interface areas in irradiated 5052 aluminum alloy

Understanding the stress corrosion cracking growth mechanism of a cold worked alumina-forming austenitic steel in supercritical carbon dioxide

High-temperature corrosion behavior of hot-pressed Al-based Gd2O3-W shielding materials used in spent fuel storage

Early-stage corrosion behavior of Al-based Gd2O3–W shielding composites in a simulated spent fuel wet storage environment

乏燃料储存用含Gd和W元素的Al基屏蔽复合材料的研制

Investigation of Microstructure and Nanoindentation Hardness of C+ & He+ Irradiated Nanocrystal SiC Coatings during Annealing and Corrosion

Microstructure characteristics of C+ and He+ irradiated SiCf/SiC composites before and after annealing

Microstructure and its effect on mechanical and thermal properties of Al-based Gd2O3 MMCs used as shielding materials in spent fuel storage

Early corrosion behaviour of irradiated FeCrAl alloy in a simulated pressurized water reactor environment

Ball-milling properties and sintering behavior of Al-based Gd2O3–W shielding materials used in spent-fuel storage

Stress Corrosion Behaviors of 316LN Stainless Steel in a Simulated PWR Primary Water Environment

研究方向